AEP-NRC-2012-64, Notification of Impact to Physics Testing Results from Fuel Vendor Modeling Error
| ML12250A660 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/23/2012 |
| From: | Gebbie J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2012-64 | |
| Download: ML12250A660 (2) | |
Text
INDIANA MICHIGAN Indiana Michigan Power p310 R
One Cook Place Bridgman, MI 49106 A unit ofAmerican Electric Power I ndianaMichiganPower.com August 23, 2012 AEP-NRC-2012-64 10 CFR 50.4 Docket No.:
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant NOTIFICATION OF IMPACT TO PHYSICS TESTING RESULTS FROM FUEL VENDOR MODELING ERROR
Reference:
- 1.
Letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Unit 1 Cycle 23 End of Life Moderator Temperature Coefficient Limit Report,"
AEP-NRC-2011-37, dated September14,2011, NRC Agencywide Documents Access and Management System (ADAMS) Accession No. ML11270A095.
By Enclosure 3 of Reference 1, I&M, the licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, committed to update the NRC with the results of the fuel vendor analyses regarding the physics testing modeling error identified in the Unit 1 Cycle 23 End of Life Moderator Temperature Coefficient Limit Report.
The fuel vendor's analysis concluded that, for D. C. Cook Unit 1 Cycles 21, 22, 23, and 24 and Unit 2 Cycles 16, 17, 18, and 19, the results from each unit and cycle's specific Subcritical Physics Testing (SPT) are considered valid.
This was determined by the examination of additional (other than SPT) parameters that corroborate the measured Isothermal Temperature Coefficient (ITC).
The measured vs. predicted Inverse Count Rate Ratio for every sub critical rod worth measurement application at CNP was examined to confirm the constructed core is accurately represented by the designed core. In addition, the actual All Rods Out (ARO) Boron Endpoint was compared to the predicted ARO Boron Endpoint; their consistency provides assurance that the ITC value is close to the predicted ITC.
U. S. Nuclear Regulatory Commission AEP-NRC-2012-64 Page 2 This letter contains no new or revised regulatory commitments.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Joel P. Gebbie Site Vice President KMH/jmr c:
C. A. Casto, NRC Region III J. T. King, MPSC S. M. Krawec, AEP Ft. Wayne, w/o enclosures MDEQ-RMD/RPS NRC Resident Inspector P. S. Tam, NRC Washington DC